Identification of initiating events for pressurized water reactor accidents
Creators
- 1. Nuclear Engineering Division, Institute of Nuclear Energy Research, No. 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China)
- 2. Department of Engineering and System Science, National Tsing Hua University, 101, Section 2 Kuang Fu Rd., Hsinchu 30013, Taiwan (China)
Description
In order to aid operators in identifying the different initiating events as defined in the Final Safety Analysis Report (FSAR), we develop a novel identification procedure. The procedure is based on the monitoring of three key system parameters in a pressurized water reactor (PWR), i.e., the pressure, the average temperature, and the temperature difference of the hot-leg and cold-leg of the reactor coolant system. By monitoring the system thermal state diagram in a pressure-temperature space, an operator can easily identify what initiating event is taking place while a static point in the diagram starts to move. The event data pool is first established by storing the transient analysis results for events of different types using the optimal estimated RELAP5 model. Since the variation ranges of system key parameters at a specific time represent the specific character for each initiating event, the identification procedure can easily determine which cases in which the event data pool can be fitted to on-line data using only variation range comparison without complex calculations. This identification method is believed to be able to help the plant operator to identify the different events and then execute the Emergency Operating Procedure more effectively.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2010.06.012Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2010.06.012;
- PII
- S0306-4549(10)00214-8;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 37
- Journal Issue
- 11
- Journal Page Range
- p. 1502-1512
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 42010488
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Descriptors DEI
- COMPARATIVE EVALUATIONS; EMERGENCY PLANS; PHASE DIAGRAMS; PRESSURE CONTROL; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR KINETICS; SAFETY ANALYSIS; SAFETY REPORTS; TEMPERATURE GRADIENTS; TEMPERATURE MONITORING
- Descriptors DEC
- ACCIDENTS; CONTROL; COOLING SYSTEMS; DIAGRAMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; EVALUATION; INFORMATION; KINETICS; MONITORING; POWER REACTORS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.